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Fretting wear behavior of Cr coated Zr-1Nb alloy cladding in high temperature high pressure water
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1.Nuclear Fuel and Materials Department,China Nuclear Power Research Institute;2.Institute of Materials,Shanghai University;3.Instrumental Analysis & Research Center, Shanghai University;4.Instrumental Analysis & Research Center, Shanghai University, Shanghai

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    Abstract:

    The fretting wear behaviors of Cr-coated Zr-1Nb cladding tube with different griding pairs in simulated PWR primary water environment at 290 °C and 310 °C were studied by using three-dimensional optical surface profilometer, scanning electron microscope, electron back scattered diffraction and energy dispersive X-ray spectrometer. The results showed that the fretting wear behaviors between the Cr-coated Zr-1Nb cladding and griding pairs (i.e., Zr-4 dimple or Inconel 718 spring) were both dominated by the adhesive wear mechanism, accompanied by material transfer from the grinding pair to the Cr-coated cladding. With the increase of temperature, the fretting wear resistance of the Cr-coated cladding was decreased, as manifested by increased surface wear depth and volume. However, the fretting wear mechanism still remained unchanged within the temperature range tested in this work. In addition, the wear degree of the Cr-coated cladding with Zr-4 dimple was greater than that with Inconel 718 spring, which was thoughted to be related to the hardness and contact mode of the grinding pair.

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[Liao Yehong, Dai Gongying, Yan Jun, Lin Xiaodong, Peng Zhenxun, Liang Xue, Li Yifeng, Xue Jiaxiang, Li Qiang. Fretting wear behavior of Cr coated Zr-1Nb alloy cladding in high temperature high pressure water[J]. Rare Metal Materials and Engineering,2024,53(10):2843~2851.]
DOI:10.12442/j. issn.1002-185X.20230530

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History
  • Received:August 29,2023
  • Revised:September 22,2023
  • Adopted:October 07,2023
  • Online: October 17,2024
  • Published: September 27,2024